A selective separation method for 93Zr in radiochemical analysis of low and intermediate level wastes from nuclear power plants
作者： T. C. Oliveira , R. P. G. Monteiro , A. H. Oliveira
DOI: 10.1007/S10967-011-1097-8
关键词: Isotopes of zirconium 、 Zirconium 、 Radionuclide 、 Extraction (chemistry) 、 Liquid scintillation counting 、 Radiochemistry 、 Standard solution 、 Low-level waste 、 Chemistry 、 Neutron activation 、 Chromatography
摘要: The zirconium isotope 93Zr is a long-lived pure β-particle-emitting radionuclide produced from 235U fission and neutron activation of the stable 92Zr thus occurring as one radionuclides found in nuclear reactors. Due to its long half life, interest for performance assessment studies waste storage or disposal. Measurement difficult owing trace level concentration low activity wastes further because certified standards are not frequently available. A radiochemical procedure based on liquid–liquid extraction with 1-(2-thenoyl)-3,3,3-trifluoroacetone xylene, ion exchange Dowex resin selective using TRU has be carried out order separate matrix analyze it by liquid scintillation spectrometry technique (LSC). To set up separation 93Zr, tracer solution 95Zr was used follow behavior during process γ-ray through measurement 95Zr. Then, protocol applied (LLW) intermediate (ILW) power plants. efficiency detection 63Ni determination matrices analyzed. limit 0.05 Bq l−1 obtained standard solutions sample:cocktail ratio 3:17 mL OptiPhase HiSafe 3 cocktail.
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